F70 辐射防护与监测综合 标准查询与下载

GB 11850-1989 反应堆退役辐射防护规定

本标准规定了反应堆退役的辐射防护标准、原则、基本要求与措施。 本标准主要适用于生产堆的退役，也适用于研究试验堆的退役。

Regulation for radiation protection of reactor decommissioning

GB 8999-1988 电离辐射监测质量保证一般规定

本规定为制定电离辐射（以下简称辐射）监测质量保证计划提供一般原则，它适用于从事辐射防护工作的所有部门。

General rule of quality assurance for ionizing radiation monitoring

GB 5172-1985 粒子加速器辐射防护规定

本规定适用于加速粒子的单核能量低于100MeV的粒子加速器（不包括医疗用加速器和象密封型中子管之类的可移动加速器）设施。

The rule for radiation protection of particle accelerators

DIN EN ISO 20046:2021 放射防护. 使用荧光原位杂交(FISH)易位试验评估电离辐射暴露的实验室性能标准(ISO 20046-2019); 德文版本EN ISO 20046-2021

The purpose of this document is to provide criteria for quality assurance (QA), quality control (QC) and evaluation of the performance of biological dosimetry by cytogenetic service laboratories.This document addresses: a) the responsibilities of both the customer and the laborat

Radiological protection - Performance criteria for laboratories using Fluorescence In Situ Hybridization (FISH) translocation assay for assessment of exposure to ionizing radiation (ISO 20046:2019); German version EN ISO 20046:2021

T/CIRA 5-2020 辐照业务管理信息系统基本功能

辐照业务管理信息系统功能包括业务功能要求和其他功能要求。 辐照业务管理信息系统业务功能要求包括客户管理、仓储管理、生产管理、质量管理、设备管理、财务管理等6类。 辐照业务管理信息系统其他功能要求包括报表管理、用户管理、权限管理、日志管理、数据字典管理、数据备份管理等6类。

Basic functions of management information system in irradiation business

DB4403/T 22-2019 城市辐射防控γ射线成像探测系统技术规范

本标准适用于具备成像定位功能的γ射线探测系统。本标准适用的γ射线成像探测系统可用于人流物流密集的公共场所的辐射防控，如地铁、口岸、仓库和集装箱堆场、核电设施、医院、展览会场、运动场所、矿产资源等城市区域的辐射防控。

Technical specifications for gamma-ray imaging detection system for urban radiation prevention and control

NB/T 20531-2018 核电厂主控室可居留性评价用大气弥散因子分析方法

Atmospheric dispersion factor analysis method for habitability evaluation of nuclear power plant main control room

NB/T 20530-2018 压水堆核电厂运行状态设计基准源项分析准则

Criteria for source term analysis of design basis for pressurized water reactor nuclear power plant operating conditions

NB/T 20529-2018 压水堆核电厂辐射防护设计准则

Design Guidelines for Radiation Protection of Pressurized Water Reactor Nuclear Power Plants

NB/T 20522-2018 核电厂堆芯中子通量测量指套管涡流检测

Nuclear power plant core neutron flux measurement refers to casing eddy current testing

ISO 12749-5:2018 核能,核技术以及放射防护.词汇.第5部分:核反应堆

This document encompasses the collection of terms, definitions, notes and examples corresponding to nuclear reactors, excluding quantitative data. It provides the minimum essential information for each nuclear reactor concept represented by a single term. Full understanding of concepts requires background knowledge of the nuclear field. It is intended to facilitate communication and promote common understanding. The scope of this document covers the whole field of nuclear reactors at a broad surface level.

Nuclear energy, nuclear technologies, and radiological protection - Vocabulary - Part 5: Nuclear reactors

DIN EN ISO 15382:2017 辐射防护.眼内晶体,皮肤和四肢的剂量监测程序(ISO 15382-2015);德文版本EN ISO 15382-2017

This standard specifies procedures for individual monitoring of radiation exposure of the skin, extremities (hands, fingers, wrists, forearms, feet and ankles), and lens of the eye. It covers practices which involve a risk of exposure to photons in the range of 8 keV to 10 MeV and electrons and positrons in the range of 60 keV to 10 MeV.

Radiological protection - Procedures for monitoring the dose to the lens of the eye, the skin and the extremities (ISO 15382:2015); German version EN ISO 15382:2017

DIN ISO/TS 18090-1:2017 辐射防护. 基准脉冲辐射特性. 第1部分: 光子辐射(ISO/TS 18090-1-2015)

Radiological protection - Characteristics of reference pulsed radiation - Part 1: Photon radiation (ISO/TS 18090-1:2015)

NB/T 20470-2017 核电厂选址假想事故源项分析准则

Criteria for analysis of hypothetical accident source terms for nuclear power plant siting

ISO 18417:2017 核设施的碘炭吸附剂. 测定吸附能力指数的方法

Iodine charcoal sorbents for nuclear facilities - Method for defining sorption capacity index

BS ISO 16639:2017 核设施工作场所空气中放射性物质活动浓度的监测

Surveillance of the activity concentrations of airborne radioactive substances in the workplace of nuclear facilities

ISO 16639:2017 监测 核设施工作场所气载放射性物质的活性浓度

Surveillance of the activity concentrations of airborne radioactive substances in the workplace of nuclear facilities

ASTM E3105-17 减轻放射性污染传播的永久涂层的标准规格

1.1 This specification is intended to provide a basis for identification of non-removable permanent coatings and fixatives as a long-term measure used to immobilize radioactive contamination, minimize worker exposure, and to protect uncontaminated areas against the spread of radioactive contamination. 1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. 1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Specification for Permanent Coatings Used to Mitigate Spread of Radioactive Contamination

ASTM E3104-17 减轻放射性污染传播的可剥离和可去除涂层的标准规格

1.1 This specification is intended to provide a basis for identification of strippable/removable materials used to immobilize radioactive contamination, minimize worker exposure, and facilitate subsequent decontamination or to protect uncontaminated areas against the spread of radioactive contamination. 1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. 1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Specification for Strippable & Removable Coatings to Mitigate Spread of Radioactive Contamination

ASTM C1831/C1831M-17 伽马辐射屏蔽性能试验的标准指南

5.1 Shielding performance testing should be performed to verify analytical predictions of shielding effectiveness, compliance with design requirements, and determine the location(s) of shielding deficiencies that may require either supplemental shielding, design modification, or changes to operating methods and procedures to resolve. 5.2 Dose rates higher than adjacent shielding may be expected in the vicinity of master-slave manipulator penetrations as a result of cable or tape clearance requirements within the mechanisms where they pass through the shield walls. This is true even with supplemental shielding installed in the manipulator through tube. 5.3 Similar to manipulator penetrations, when sources are placed directly in front of penetrations and gaps resulting from access doors or panels, radiation levels directly on the other side of the gaps or penetrations may be higher than levels in adjacent shielding or analytical predictions. If these test configurations are representative of how the shielded enclosure will actually be operated (that is, the test configuration is representative of engineered source and normally occupied work locations) than the additional expense of designing or modifying the shielded enclosure should be considered if that location is normally occupied and will result in a significant increase of dose rates to personnel. 5.4 Frames around shield windows may have a higher potential for shielding deficiencies. 5.5 Shield walls constructed of concrete may be subject to the formation of void spaces that could result in diminished shielding performance. 5.6 Background radiation levels in the area where the dose measurement data are being gathered shall be monitored and their contribution to measured dose rates accounted for in the data analysis as part of the test report. 1.1 This guide identifies appropriate test methods for determining the sufficiency of radiological shielding for hot cells and shielded enclosures. 1.2 After constructing or modifying radiological shielding, it is necessary to verify that shielding performance meets or exceeds the shielding performance requirements. This is typically accomplished using sealed test sources of much less activity than the design basis. This allows for modifications or correction of any discrepancies identified before the commissioning of the hot cell. 1.3 The guidance and practices recommended by this guide are applicable to both new and existing shielded facilities and enclosures for evaluating shielding suitability and locating the existence of shine paths or other shielding anomalies that result from design, manufacture, or construction. 1.4 Two types of testing may be performed. 1.4.1 Shielding performance verification testing provides evidence that the shielding configuration is sufficient for meeting established performance criteria and for identifying......

Standard Guide for Gamma Radiation Shielding Performance Testing